Text

Proposed Tech Specs Revising TS 3/4.4.1.4.1, Cold Shutdown-Loops Filled, TS 3/4.4.1.4.2 Cold Shutdown -Loops Not Filled, TS 3/4.9.8.1, Shutdown Cooling & Coolant Circulation,High Water Level
	ML20126E788
Person / Time
Site:	San Onofre
Issue date:	12/24/1992
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20126E759	List: ML20126E757; ML20126E769; ML20126E788;
References
	NUDOCS 9212290331
	Download: ML20126E788 (59)
	v • d • e

. _ _ _. _ _ _ _ _ _ _ _ -.

1 DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-10/15-411 1

This is a request to revise Technical Specification (TS) 3/4.4.1.4.1," Cold Shutdown - Loops filled," TS 3/4.4.1.4.2 " Cold Shutdown - Loops Not Filled,"

TS 3/4.9.8.1, " Shutdown Cooling and Coolant Circulation, High Water Level," TS 3/4.9.8.2, " Shutdown Cooling and Coolant Circulation, Low Water Level," and their associated Bases.

Existina Specifications Attachment A - Unit 2 Attachment B - Unit 3 Proposed Specifications Attachment C - Unit 2 Attachment D - Unit 3 Supportina Fiqures Attachment E Post Modification Spent Fuel Pool Coolina Administrative Controls (Information Only)

Attachment F DESCRIPTION Technical Specification (TS) 3/4.4.1.4.1, " Cold Shutdown - Loops Filled," and TS 3/4.4.1.4.2 " Cold Shutdown - Loops Not Filled" provide the Limiting (SRs)

Conditions for Operation (LCO), Actions, and Surveillance Requirements for the reactor coolant loops and shutdown cooling system during cold shutdown.

TS 3/4.9.8.1, " Shutdown Cooling and Coolant Circulation-High Water Level," and TS 3/4.9.8.2, " Shutdown Cooling and Coolant Circulation-Low Water Level," provide the LCO, Actions and SRs for the shutdown cooling and coolant circulation system during refueling operation.

The purpose of this PCN is to revise TS 3/4.4.1.4.1, TS 3/4.4.1.4.2, TS 3/4.9.8.1, and TS 3/4.9.8.2 to allow for the use of Containment Spray (CS) pumps in place of Low Pressure Safety Injection (LPSI) pumps to perform Shutdown Cooling (SDC) during Modes 5 and 6 of operation. This will allow for maintenance of both LPSI pumps, the Component Cooling Water (CCW) cross train isolation valves, and the SDC system without the need to fully offload the core into the Spent Fuel Pool (SFP).

The plant modification and proposed technical specification changes will allow required and preventative maintenance while maintaining required cooling systems operable.

The Plant modifications will allow use of the SDC system, using either CS pumps or LPSI pumps, for SFP cooling.

Extensive thermal hydraulic analysis indicates that CS pumps can provide SDC flow with no reduction in the margin of safety.

k ADO 1

P

\\

.a

I The.SDC system will only be used to cool the SFP in Modes 5 and 6.

This-change has _no effect on TSs, because the SFP_ cooling system is not governed by current TSs, but rather by Administrative Controls. Although the plant-modification will physically allow the use of the SDC system in any Mode of operation, the use will be prohibited if the SDC system, the CS pumps or the-LPSI pumps are required to be OPERABLE by Technical Specifications.

(e.g.

When only one train of SDC is required to be OPERABLE by Technical-Specifications, then, one OPERABLE train will be dedicated to meet the specification and the other train will be allowed to cool the spent fuel pool.)

This PCN also requests a change to the UFSAR wording approved-by Amendments 94 and 84 to the Units 2 and 3 operating licenses.

This change will remove the requirement for a full core offload.

Changes to the Unit 2 and 3 TSs are requested as follows:

a TS 3/4,4.1.4.1 1.

Add a third footnote to the " Shutdown Cooling train" as it appears in items (a.3), (a.4) and (b) of the LC0 to allow for use of CS_ pumps in place of LPSI pumps to provide SDC flow beginning no sooner-than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the reactor is sub-critical and provided the reactor coolant system is fully depressurized and vented in accordance with TS 3.4.8.3.1.b.

2.

Revise the first footnote in the present TS to recognize that the CS pump may be providing SDC flow.

3.

Revise the associated Bases of TS 3/4.4.1.4.1 to document the bas'is for the above TS changes.

TS 3/4.4.1.4.2 1.

Add a third footnote to the LC0 to allow for-use of CS pumps in place of LPSI pumps to provide SDC-flow beginning no sooner than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after -

the reactor is sub-critical and provided the reactor coolant system is fully depressurized and vented in accordance with TS 3.4.8.3.1.b.

2.

Revise the second footnote in the present TS to recognize that-the CS pump may-be providing SDC flow.

3.

Revise the associated Bases of TS 3/4.4.1.4.2 to document the basis.for the above.TS changes.

-TS 3/4.9.8.1 1.

Add a footnote.to the LC0 to allow use of CS pumps in place of LPSI pumps to provide shutdown cooling flow.

2.

Revise the associated Bases of TS 3/4.9.8 to document the basis for the above TS changes.

~

l'

. TS 3/4.9.8.2 1.

Add a footnote to the LCO to allow use of CS pumps in place of LPSI pumps to provide shutdown t.coling flow.

The following changes to the UFSAR wording, which was approved by Amendment Nos. 94 and 84 to the Unit 2 and 3 operating license, are also requested:

Proposed Changes to the UFSAR 1.

The paragraph whicn was added to Section 9.1.3.2 SYSTEM DESCRIPTION between the second and third paragraph on page 9.1-14 by Amendment Nos. 94 and 84 should be revised as follows:

The shutdown cooling system is a safety related, seismically qualified system which is powered by a class 1E electrical system.

The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the spent fuel pool temperature 1ower than the-spent-fue -pool canib'e'maintainsd! b.pltlisf spent fue1Tpool? cooling system. Duv4ng Yfdll'sereTcfflJdWos-the reet+r vessel Whensom'p'onentsjof ?the shutdown cooling system are not required tol be10PERABLE by?technicalispecificatibns-to-be oper,Me-for-rda c tFde rc2esoMng,4 ' th en ! on e S tra i n t o f ~' t h e shutdown cooling system (consisting of"at"le~astTLPSI pump orJ1 containment 3prap[ pump, I heat exchanger, flow path to and fr6m the SFP, 'and the " associated Diesel Generator) may be aligned to cool the spent fuel pool. Ad di t i oiial lyWdifri jig) MOD E' 6Tsi ttF th 6 reactor? refuelingfcavitf wateriler11 greaterf than(or;equaltto;23 feet!aboveithe reactorlflange;? thel,0CSsystem?(consisting offat~

least;2; pumps?(eithertitLPSlipump?End?ISCSjpumdort2iCSTpumps)3 11 SDC Lh; eat? exchanger, tfl ow1 pa thse tolandi fromit ie LRCSTand ySFP Uahd -

the-associated DieselsGeneratoQmaf;befalifgnedf toj coolj bothithe" SFPfand?thehreactor core.

2.

The second to the last paragraph of Section 9.1.3.3 SAFETY EVALUATION on page 9.1-18 should be revised as follows:

"The shutdown cooling system, if available, may'be used as an alternative means of cooling the spent fuel pool when the full ecre is removed frcm the reaeter vessel. This covers the possibility referred to under the remarks column of table 9.1-3."

SYSTEM DESCRIPTION The SDC system is used to remove heat from the RCS during shutdown and post-shutdown periods. During normal plant operation major components of the SDC.

system (the LPSI pumps and the SDC heat exchangers) are aligned for emergency core cooling and containment cooling functions.

The LPSI system is not needed for emergency core cooling in Modes 5 and 6 and therefore is available to provide SDC.

In their SDC-function the LPSI pumps take " -tion from RCS hot leg number 2.

tieat is removed by circulating this flow tnrough the SDC heat exchangers. The cooled flow returns to the RCS through at least two of the-four LPSI headers connected to the cold legs.

The proposed plant modification

'4

' will provide the capability to substitute a CS pump for a LPSI pump on either or both trains to provide SDC flow provided the RCS is fully depressurized and vented in accordance with TS 3.4.8.3.1.b.

The RCS must be vented to protect the CS system and the SDC system from over-pressurization due to_-the discharge head of the CS pumps being greater than the discharge head of the LPSI pumps.

Venting is being required because the Low Temperature Over Pressure relief setpoint is being maintained and the affected components'will not be rerated.

SYSTEM CONFIGURATION CHANGES The normal LPSI/CS system configuration in MODE 1 is shown in Figure 1.

The proposed system contiguration change that will provide the capability to use the CS pumps in place of the LPSI pumps for SDC cooling and/or SFP cooling is shown in Figure 2.

As depicted in Figure 2, added piping and valves will allow a flow path to the suction side of the CS pumps to be established by connecting the LPSI/SFP suction line to the CS suction line. Added piping and-valves downstream of the SDC heat exchangers will allow a flow path to _be established from the CS system to the SFP cooling system return line.

The proposed changes described below are shown in Figure 2 with the valves in the required position for MODE 1 operation, all other_ figures show valves in the position required to support the specified alignment:

1.

Install a new pipe line between the SFP suction pipe line to the LPSI pumps and the suction side of the CS Pumps. Manual-isolation gate valves MU992 and MU993 will be installed on the suction side of each CS pump.

This location is selected so SFP cooling can be achieved by using CS Pumas and isolation of the LPSI/SDC system from the SFP supply line can )e maintained.

2.

Install manual gate valve MU994 at a location downstream of existing valve MUO33 to provide the capability to-isolate the-LPSI/SDC_ system completely from the SFP. This valve will also provide positive isolation against ~ possible flow diversion during. other modes of operation.

3.

Relocate existing temperature element (TE) TE0351-Y to a location further downstream as shown in Figure 2 and retag it as TE8148.

Also, relocate TE8149 to a location further downstream as shown in Figure 2.

These changes will allow monitoring the SDC heat exchanger inlet temperature regardless of the operating pump (CS or LPSI).

4.

The existing spectacle blind flange, located upstream of manual.

valve MUO33,. is no longer required to 3rovide isolation.

Double isolation using manual valves is possi)le due to the valves discussed in items 1 and 2.

The spectacle blind will be placed in the normally open position. The spectacle blind is not being -

removed so that it will-be available to provide isolation during hydrostatic testing of the piping being installed by this modification or for other future maintenance work.

S.

Install pipes and manual gate valves MU105 and MU106 to cross connect-CS trains A and B to the SFP cooling line downstream of the i

. SDC heat exchangers. Manual globe valve MU104 and a restricting orifice will be installed to provide double valve isolation and flow throttling capabilities.

6.

The existing spectacle blind flange, located downstream of the manual gate _ valve, MUO18 is no longer required to provide isolation.

Double isolation using manual valves is possible due to_the valves discussed in item 5.

The spectacle blind will be placed in the normally open position. The spectacle blind is not being removed so that it will be available to provide isolation during hydrostatic testing of the piping being installed by this modification or for other future maintenance work.

7.

Install two manually operated normally locked-open gate valves; the-first valve MU367 will be installed upstream of Motor Operated Valve (MOV) 2HV8152, and the second valve MU366 will be installed upstream of MOV 2HV8153. These new valves will allow for maintenance of valves 2HV8152 and 2HV8153 while the core is in the reactor vessel.

8.

Two new thermal relief valves (2PSV1575, 2PSV9317) will be installed on the cross-connect piping and the spent fuel pool return line to comply with the ASME Code, Subsection III NC 3612.4.

The above modifications will not involve any changes to the electrical logic nor the addition of any electrical components with the exception of relocating existing temperature elements TE8149 and TE0351-Y (retagged as TE8148.) No electrical or instrumentation setpoints will be added, deleted, or. revised.due to the above modifications, and no TS setpoints or automatic trip functions -

will be modified.

DISCUSSION The proposed plant mortifications with the requested technical specification changes allow the Containment Spray (CS) pumps, whi_ch during Modes 5 and 6 perform no safety related function, to be used as a second safety related pumping device on each train of the Shutdown Cooling (SDC) system.

This increases the plant's flexibility in maintaining SDC-flow while performing maintenance. The proposed changes to the reactor coolant system (RCS) TSs 3/4.4.1.4.1, 3/4.4.1.4.2, 3/4.9.8.1 and 3/4.9.8.2 allow for use of CS pumps in l

place of Low Pressure Safety Injection (LPSI) pumps to perform SDC during Modes 5 and 6 of operation.

-This flexibility provides both an increase in safety as well as a cost savings by potentially reducing refueling outage duration.

In Modes 5 and 6, two additional safety related pumps wil! be available to provide SDC flow. During refueling when only one train of SDC is required,-the other train is usually not available due to maintenance. Thus, if an unplanned loss of a LPSI pump occurs, backup cooling is not readily available and core alteration activities would have to be halted,- causing delay in the outage.

This modification will allow a CS pump to maintain SDC flow in the event a LPSI pump is lost, maintaining core cooling and allowing core alteration activities to continue.

This change would also provide alternatives to maintenance which currentlyL would require fully offloading the core into the Spent Fuel Pool (SFP), such as maintenance on the component cooling water cross tie isolation valves or

4

. other evolutions resulting in the loss of the CCW non-critical loop.-

The modifications will also provide an alternate means of SFP cooling by using SDC heat exchangers with LPSI and/or CS pumps in Modes 5 and 6 of operation.

Currently, the SDC system may be used to provide SFP cooling with a requirement to completely offload the core..The proposed modification will allow removal of SFP cooling system components for maintenance without the full core offload requirement. Operation of the SFP cooling system is governed by Administrative Controls which are included in Attachment F for information.

Modifications will also provide the capability of performing concurrent SDC and SFP cooling using one SDC heat exchanger with flow provided by a LPSI pump and a CS pump or two containment spray pumps in Mode 6 of operation.

Analysis Thermal hydraulic analysis was performed to evaluate the capability of CS pumps to perform SDC and/or SFP cooling using the proposed system configuration.

It was concluded that CS pumps can be used with no reduction in a margin of safety to perform the following functions:

CS Pumps for SDC in MODES 5 and 6 1)

This alignment allows the CS pumps to be used for chutdown cooling in lieu of the LPSI pumps in Modes 5 or 6.

The coolant flow path with this system alignment is shown in Figure 3.

RCS cooling will begin no sooner-than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter the reactor is sub-critical,- when the plant has' been cooled to a Mode 5 temperature of 200'F, and with the RCS depressurized and vented in accordance with TS 3.4.8.3.1.b.

The-proposed changes to TSs 3.4.1.4.1, 3.4.1.4.2, 3.9.8.1, and 3.9.8.2 are required to support this alignment.

CS Pumps for Both SDC and SFP Coolina-in MODE 6 2)

This alignment provides an alternate means of both SDC and SFP cooling by two CS pumps, using one SDC heat-exchanger in Mode 6 with the reactor refueling cavity water level greater than or equal to 23 feet above the -

reactor vessel flange.

This system alignment can be used when both the-SFP cooling trains and LPSI pumps are removed'from service for maintenance.

The coolant flow path with this system alignment is shown -

in Figure 4.

The proposed changes to TS 3.9.8.1 and the UFSAR are t

required to support this alignment.

Operation with this system alignment may be employed with the following restrictions:

a.

The reactor head is removed.

b.

The fuel transfer gate and fuel transfer tube are open and the refueling cavity is flooded to allow for the equalization of water

i 4

3 '

levels between the SFP and the reactor cavity, c.

The reactor cavity water level is greater than or equal to 23 feet above the reactor vessel flange.

LPSI Pump and CS Pump for SDC and SFP Coolina Combined Flow in MODE 6 3)

This alignment provides an alternate means of SFP cooling by one CS pump, while SDC is being performed by one LPSI pump in Mode 6 with the reactor refueling cavity water level greater than or equal to 23 feet above the reactor vessel flange. Only one SDC heat exchanger will be used in this mode of operation. This system alignment will be required during the repair of CCW non-critical loop isolation. valves for one of the CCW trains.

The coolant flow path for this system alignment is shown in Figure 5.

The proposed changes to TS 3.9.8.1 and the UFSAR are required to support this alignment.

Operation with this system alignment may be employed with the following restrictions:

a.

The reactor head is removed.

b.

The fuel transfer gate and fuel transfer tube are open and the refueling cavity is flooded to allow for the equalization of water levels between the SFP and the reactor cavity, c.

The reactor cavity water level is greater than or equal to 23 feet above the reactor vessel flange.

CS or LPSI Pumns for SFP Coolina in MODES 5 and 6 4)

This alignment provides an alternate means-of SFP cooling in MODES 5 or 6 by 1 or 2 CS pumps or 1 LPSI pump and 1 or 2 SDC heat exchangers in -

lieu of either 1 or 2 trains of SFP cooling.

The coolant flow path-utilizing a CS pump is shown in Figure 6.

This alignment using a LPSI pump is already approved by the'NRC for use during full core offload.

The proposed change to the UFSAR is required to support this alignment for conditions other than full core offload.

- SCE currently takes credit for the SDC system, when it is available, as an alternate cooling system for the SFP during complete core offloads.

Calculations performed in support of the Units 2 and 3 reracking project show

- the SDC system (1. pump and I heat exchanger) can maintain the SFP temperature approximately 12 degrees cooler than the SFP cooling system (2 pumps and 2 heat exchangers) during a full core offload. Therefore, the function of cooling the SFP is not only maintained but improved.

The shutdown cooling system is a safety related, seismically qualified system which is powered by a class 1E electrical system.

The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the. spent fuel pool temperature lower than can be maintained with the spent fuel pool cooling system. When the shutdown cooling system is not required to be operable for reactor core cooling, the shutdown cooling system (consisting of at least 1

. LPSI pump or 1 CS pump, I heat exchanger, Flow Path to and from the SFP, and the associated Diesel Generator) may be aligned to cool the spent fuel pool.

During refueling outages there is only one complete train to provide a heat path from the SFP to the ultimate heat sink:

one or two train (s) of_the SFP cooling system, one train of CCW, one train of the Salt Water Cooling (SWC) system, and the associated Diesel Generator. -Additionally, TS 3/4.9.8.1 only requires one train of SDC to be operable.

The basis for TS 3/4.9.8 states that with the reactor head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

The proposed change will only affect the location of the fuel; the heat load from the fuel in the SFP and the fuel in the core will be the same as if all the fuel were in the SFP.

The large heat sink will be provided by both the SFP and the reactor fueling pool being connected and level maintained 23 feet above the reactor vessel flange. Therefore, the intent of the basis for TS 3/4.9.8 is met at all times during these evolutions.

Safety Analysis:

The proposed change described above shall be deemed to involve a significant hazards consideration if there is a positive finding in any of the following areas:

1.

Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

RESPONSE

No.

The function of the CS system is to remove heat from the containment atmosphere in the event of a Loss Of Coolant Accident (LOCA) or Main Steam Line Break (MSLB) inside containment.

The CS system is required for containment cooling by TSs in Modes 1, 2, and 3 of operation.

The proposed change will allow for use of CS pumps, which are an integral part of the CS systen., to perform shutdown cooling only in Modes 5 and 6 of operation._ Modifications to the-RCS that cross-tie the CS system to SDC system contain manually operated valves that will remain in the LOCKED-CLOSED position in Modes 1, 2, and 3, thus segregating the CS system from the SDC system and allowing the CS pumps to perform their containment cooling functions. Therefore, the proposed change will not increase the probability or consequences of accidents previously evaluated in the Updated Final Safety Analysis-Report (UFSAR).

During normal power operation, the SDC system is used to reduce the temperature of the RCS in post-shutdown periods from operating temperature to the refueling temperature.

The initial phase of the cocidown is accomplished by heat rejection from the steam generator to the condenser or the atmosphere. After the reactor coolant temperature and pressure have been reduced to approximately 350*F

I 9

and 376 lb/in' the SDC system is put into operation.

The proposed change will allow for the use of CS pumps in place of LPSI pumps in the SDC system after the reactor coolant has reached a temperature of 200*F and is vented in accordance with TS 3.4.8.3.1.b.

The SDC system is credited to perform long-term core cooling to maintain acceptable core temperatures until the plant is secured for all accidents except for a large break LOCA (UFSAR Section 15.6.3.3.2 and 15.6.3.2.1.5).

The proposed change is to allow SDC by CS pumps only during maintenance of SDC systems (Modes 5 and 6) and not in post-accident conditions.

Therefore, this change does not impact the performance of the SDC system during long-term core cooling.

The CS pumps are fully capable of providing the required flow rate to perform SDC in Modes 5 and 6.

In Mode 5, the CS pumps are capable of providing the required SDC cooling flow with the RCS loops filled and during mid-loop operation. The CS pumps, however, have a higher discharge head than the LPSI pumps.

To compensate for this difference, shutdown cooling by the CS pumps will only be performed when the RCS is vented in accordance with TS 3.4.8.3.1.b to preclude any 30ssibility of over-pressurization of piping in the SDC system and tie CS system.

None of the structures, systems, or components that initiate any accident described in the UFSAR will be affected by this change.

Therefore, this proposed change will not constitute an increase in the probability of an accident previously evaluated.

There will be no increase in any accident probability as a result of this change because cooling to the SFP is maintained available at all times.

The rerack license amendment request, PCN 287, provides an analysis for a complete loss of cooling that results in boiling of the spent fuel pool.

This was evaluated by the NRC and documented in the Safety Evaluation Report on the Units 2 and 3 Reracking, issued May-1, 1990.

The only potential accident remaining is a release of radioactivity from damaged fuel assemblies in the SFP. Both the SFP cooling system and the SDC systems are designed to maintain cooling capabilities to both the SFP and the core, respectively, which prevents this potential accident from occurring.

In addition, the cooling capacity of each train in the SDC system is greater than the cooling capacity of the SFP cooling system.

During refueling outages there is only one complete train required to provide a heat path from the SFP to the ultimate heat sink:

one or two train (s) of the SFP cooling system, one train of CCW, one train of SWC, and the associated Diesel Generator.

The above is true whether or not the SDC system is available for back-up.

The proposed change will only affect the location of the fuel.

The heat load from the fuel in the SFP and the fuel in the core will be the same as if all the fuel were in the SFP.

The large heat sink will be provided by both the SFP and the reactor fueling pool being connected and level maintained 23 feet above the reactor vessel I

1

B 4 flange._ Therefore, the intent of the basis for TS 3/4.9.8 is met at all times during these evolutions.

Therefore, there is no increase in the probability or consequences of an accident previously evaluated.

2.

Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

RESPONSE

No.

The proposed change does not affect any structures, systems, or components which initiate any accident. All new components (manually operated valves and thermal wells for temperature elements) are designed to Seismic Category 1, ASME Section III Class 2,

"N" stamp, and meet the current design criteria for the Shutdown Cooling system and the Containment Spray system.

The isolation valves at the system interfaces are designed at higher pressure and temperature ratings than the system design requirement.

The cross-tie piping will be equipped with thermal relief valves to protect the pipes from over-pressurization if the interface valves between the SDC suction line and the cross-tie were to leak.

In addition, the cross-tie piping will not be subjected to the high pressure that the SDC system is generally subjected to during normal post-shutdown cooling since the CS pumps will only be used for SDC in Modes 5 and 6 after the RCS has been fully depressurized and vented.

According to UFSAR Section 5.4.7.1, a LOCA during shutdown cooling is not considered to be credible since the-total stress-in any RCS component will be considerably less than the total stress at design pressure. This will be a-valid assertion after the implementation of this proposed plant modification, since the CS pumps will be used in Modes 5 and 6 when the RCS system is fully depressurized and vented. Since the pipes of the cross-tie are routed through the same areas where-the SDC system pipes are located, no new detection methods are required to determine the condition of the cross-tie pipes.

Also, no new actions to mitigate the consequences from a break / crack in the cross-tie piping will be required other. than the existing actions for the SDC system.

The proposed change will allow for use of CS pumps to provide 50C flow.

The CS pumps are capable of providing the required minimum l

flow rate for SDC in Modes 5 and 6.

The CS pumps have a higher i

discharge head than the LPSI pumps, and to compensate for this difference, shutdown cooling by CS pumps will only be performed after the RCS has been depressurized and vented in accordance with TS 3.4.8.3.1.b.

This will protect pipes of the SDC system and the CS system from inadvertent over-pressurization.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

+ 3.

Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?

RESPONSE

No.

The-proposed change does not affect the safety related functions of the SDC system or the CS system. The CS system will continue to perform its containment cooling function in Modes 1, 2, and 3, since the CS pumps will only be used in Modes 5 and 6 when the CS pumps are segregated from the CS system and the'RWST by LOCKED-CLOSED isolation valves.

The thermal hydraulic analysis performed to support the use of CS pumps in place of LPSI pumps to perform SDC indicates no reduction in a margin of safety.

This proposed change does not cause a reduction in a margin of safety because, as before the change, only one train of cooling is-relied upon from the_ Spent fuel Pool to the Ultimate Heat Sink during mode 5 and 6.

The proposed change does not reduce the capability of heat transfer, and it does not change the number of trains required to be available -

to cool the core. The use of the SDC system has been ap) roved by the NRC as an acceptable cooling source for the SFP in.tle safety-evaluation report for the Units 2 and 3 reracking, issued May 1, 1990.

In addition, the cooling capacity of the 500 system is greater than the cooling capacity of the SFP cooling system.

Additionally, the SDC/SFP cooling mixed flow configuration provides a larger volume of water that will provide heat removal in the event that cooling flow would be interrupted. Therefore, the margin of safety is increased, not reduced during operation using the proposed alignment for the-alternate SFP cooling.

SAFETY AND SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Based on the above Safety Analysis, it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; (2) there is a reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this action will-not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.

=.

1 s

NPF-10/15-411 i

l 5-t ATTACHMENT "A" EXISTING SPECIFICATIONS UNIT 2

i REACTOR COOLANT SYSTEM b

1 COLD SHUTDOVN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 a.

At least one of the following loop (s)/ trains listed below shall be OPERABLE and in operation":

1.

Reactor Coolant Loop 1 ano its associated steam Pump ** generator and at least one associated Reactor Coolant 2.

Reactor Coolant Loop 2 and its essociated steam Pump ** generator and at least one associated Reactor Coolant 3.

Shutdown Cooling Train A.

4.

Shutdown Cooling Train 8 One additional Reactor Coolant loop / shutdown cooling train c.

shall be OPERABLE, or The secondary side water level of c.

be greater than 10% (wide range). each steam generator shall APPLICABILITY:

MODE 5, with Reactor Coolant loops filled.

ACTION:

with less than the required steam generator level a.

initiate corrective action to return the required trains OPERABLE status or restore the required level as soon as/ loops to possible.

b.

With no loop / train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required loop /

train to operation.

All reactor coolant pumps and shutdown cooling pum zed dilution of the Reactor Coolant System boron concentration e

outlet temperature is maintained at least 10'F below saturation (2) core

, and

- A Reactor Coolant pump shall not be started with one or more of the R temperature.

Coolant System cold leg temperatures less than or equal to that specifie or Table 3.4-3 when the secondary water temperature of each steam gener n

greater than 100*F above each of the Reactor Coolant System cold leg s

atures.

SAN ONOFRE - UNIT 2 3/4 4-5 AMENOMENT NO. 70 E

~

REACTOR COOLANT SYSTEM i

COLD SHUTDOWN - LOOPS F1LLEO gm i

\\

SURVE!LLANCE REQUIREMENTS I,.4.1.4.1.1 'the required Reactor Cooling pump (s), if not in operation, shall be detemined to be OPERABLE once per 7 days by verifying correct breaker align-

! C.:2 ments and indicated power availability.

4.4.1.4.1.2 The required steam generator (s) shall be determined OPERABLE by verifying the secondary side water level to be 110% (wide range) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.3 At least one Reactor Coolant loop or shutdown cooling train shall be verified to be in operation and circulating Reactor Coolant at least once i

per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

-(

I

. (..

s 1

l

'e f

NOV 0 91984 L

SAN ONOFRE

-UNIT 2 3/4 4-Sa AMENDMENT NO. 27

(

i_

l p-

~.

_ _, __ _..__ _ __,,. ; *n y;___ ;_

\\

I REACTOR COOLANT SYSTEM

,m.

?

C0LO SHUT 00% - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION

and at least one Two shutdown cooling trains shall be OPERABLE 3.4.1.4.2 shutdown cooling train shall be in operation."

MODE 5 with Reactor Coolant loops not filled.

APPLICABIt.1TYt ACTION:

With less trian the above required trains OPERABLE, immediately initiate corrective action to return the required trains to OPERABLE a.

status as soon as possible.

With no shutdown cooling trains in operation, suspend all operations involving a raduction in boron concentration of the Reactor Coolant b.

System and immediately initiato corrective action to return the required shutdown cooling train to operation.

SURVEILLANCE RE001REMENTS At least one shutdown cooling train shall be determined to be in 4.4.1.4.2 operation and circulating reactor coolant a,t least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ne shutdown cooling train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance is OPERABLE and.n operatien.

i 0testing provided the other shutcown co'oling train "The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at 1 east 10*F below saturation temperature.

s l

MW 10 EO l

3/4 4-6 AME30 MENT NO. 16 SAN ONCFRE-UNIT 2

^'

I

,o i

l d

)-

1 Rtrutt1Ng OptRaff 0ws i

3/4.9.8 $WVT00WW C00t!NG aND 000(aWT CIRCULATION

~.l.::L..

M1cs waitt Livil LIMIT!NG C040TT10N FOR OP(LATION r

3.9.8.1 A operation ) least one shutdown cooling train shall be OPERABLE and in a**tICA31LITY: M00E 6 when the water level above the top of the resetor pressure vessel flange is greater than or equal to 23 feet.

ACTICWt With no shutenwn cooling train CPERA8LI and in operation. suspend all coeretions involving an increase in the reactor cecay heat load or a reduction in toren concentration of the Reactor Coolant Systes and inmediately initiate corrective action to return the reewired shuteown cooling train to CPERA3LE and operating status as soon as possible. Close all containment penetrations provicing cirect access from the containment atmosphere to the outsice atmosphere within' 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b o

$URVE!LlaNCE Rf0VIREutNTs 4.9.8.1 At least one shutcown cooling train shall be verif tec to ce in operation and circulating reacter coolant at'a flow rate of greater than er.

eoval to 2200 rps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l.

'The shutdown cooling train say be removed from operation for we to 1 neur oer 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicini*y of the reactor pressure vessel het legs.

4

\\;.

SAN ONOFRE-UNIT 2 3/4 9 8 AMENDMENT No. 45 Y

O

g 4

s N

l t[FUtLING CPttAtteks l

-1

- ~ ^*

tow watte Ltytt t!MIT!NG CON 0ft10N FOR cptRAT10N 3.9.8.2 Two ineepensent shuthwn cooling trains shall be OPERA 8LE and at least one shutso w cooling train shall be in operation.-

ApptitAllt!TY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION With less than the recuired shutdom cooling trains CPERA8LE, a.

innediately initiate corrective action to return the requirte shut-cown cooling trains to CPERAALE status, or to establish greater than or equal to 23 feet of water soove the reactor pressure vessel flange as soon as possible.

With no shutdo w cooling train in operation, suspend all operations c.

involving a reduction in boren car. centration of the Reacter Coolant Systes and ismediately initiate corrective action to return the recuitec shutcown cooling train to operation. Close all containMnt penetrations providing cirect access from the containment etacphere to the outsics atmospnere within a hours.

o

$URVE!LLANCE Rt0VIREMEvf1

^

4.9.8.2 At least one shutcow cooling train shall be verified to be in

'i operation and circulating reactor coolant at a flow rate of greater than or equal to 2200gpa at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 9

i is: _

$AN CHOFRE UNIT 2 J/4 9-9 AMENDMENT NO. 45

.O 3_

r

/]

3/4.4 REACTOR COOLANT SYSTEM BASES

\\

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to' operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR greater than 1.31 during all normal operations and anticipated transients.

As a result inMODES1and2withonereactorcoolantloopnotinoperation,thisspecl-fication requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months since no safety analysis has beta conducted for operation with less than 4 reactor coolant pumps or less than two reactor coolant loops in operation.

In MODE 3, a single reactor e n t ' m covides sufficient heat removal capability for removing decay he m W u siv 't failure considerations require that two loops be OPERABL In MODE 4, and in MODE 5 with o. w. coolant loops filled, a single reactor coolant loop or shutdown cooling rain provides sufficient heat removal capability for removing / trains (either RCS or shutdown cooling) be OPERABLE.

decay heat; but single failure considerations require that at least two loops In MODE 5 with reactor coolant loops not filled, a single shutdown cool-ing train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam genera-tors as a heat removing component, require that at least two shutdown cooling trains be OPERABLE.

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reac-tor Coolant System.

The reactivity change rate associated with boron reduc-tions will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump in Modes 4 and 5 with one or more RCS cold legs less than or equal to that specified in Table 3.4-3 are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50.

The RCS will be protected against overpressure transients and a

will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant jo eApand into or (2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100*F above each of the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve 4.6 x 105 lbs per hour of saturated steam at the valve setpoint plus 3% accumulation.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with RCS cold leg temperature greater than that specified in Table 3.4-3.

In the event that no safety valves are OPERABLE and for RCS cold leg temperature less than or equal to that specified in Table 3.4-3, the operating shutdown cooling relief valve, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

SAN ONOFRE-UNIT 2 8 3/4 4-1 AMENDMENT HO. 70 l

F 4;

REFUELING OPERATIONS BASES 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING-(Continued)_

1.

The radiological consequences due to complete rupture of all spent 1

fuel assemblies in the spent fuel pool and the cask pool (480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses as long as spent fuel _has received a minimum of 88 days decay time.

This analysis takes no credit for fuel handling building filters (i.e., the fuel handling building hatches are open).

2.

Any.possible distortion of.all fuel assemblies and racks will not result in a critical array and K will remain less than 0.95, as a

longasfuelisstoredperTechnTN1 Specifications 5.6," Fuel _

i.

Storage," and 3.9.13, " Spent Fuel Pool Boron Concentration."-

l 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F_as required during the REFUELING H0DE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident r

and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there-is.less than 23 feet of water above the' reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a com-plete loss of decay heat removal capacity.

With the reactor vessel head're-moved and 23 feet of water above the reactor pressure vessel f1_ange, a large heat sink is available for core cooling, thus in the event of a. failure of the operating shutdown cooling train, adequate time is provided to-initiate emer-gancy procedures to cool the core.

l\\

SAN ONONFRE _ UNIT 2_.

B 3/4 9-2a AMEN 0 MENT NO. 87:

m.

i NPF-10/15-411 i

i 1

1 ATTACHMENT "B" EXISTING SPECIflCATIONS UNIT 3 0'.

~

. ~....

7 is.

is

' ' REACTOR COOLANT SYSTEM COLD SHUTOOWN --LOOPS FILLED h

LIMITING CONDITION FOR OPERATION 9p 3.4.1.4.1 a

At least m of the following loop (s)/ trains listed below h

shall be L.RABLE and in operation *:

~~

1.

Reactor Coolant loop 1 and its associated steam generator and at least one associated Reactor Coolant y

Pump **

h

~

2.

Reactor Coolant loop 2 and its associated steam p

generator and at least one associated Reactor Coolant i

ef-Pump **

' i

(

\\

p 3.

Shutdown Cooling Train A h?

4.

Shutdown Cooling Train 8 h

b.

One additional Reactor Coolant Loop / shutdown cooling train i

((;

shall be OPERABLE, or k

c.

The secondary side water level of each steam generator shall f[k be greater than 10% (wide range).

APPLICABILITY:

MODE 5, with Reactor Coolant loops filled.

ACTION:

E

.h a.

With less than the above required shutdown trains / loops OPERABLE;or with less than the required steam generator level, immediately 5

initiata corrective action to return the required trains / loops to

,j OPERABLE status or restore the required level as soon as possible.

b.

With no loop / train in operation, suspend all operations involving a g

reduction in boron concentration of the Reactor Coolant System and p

immediately initiate corrective action to return the required loop /

train to operation.

fky h

All reactor coolant pumps and shutdown cooling pumps may be de-energized p

for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided (1) no operations are permitted-that would C&Jse i

dilution of the Reactor Coolant System boron concentratiun, and (2) core f-I(

outlet temperature is maintained at least 10'F below saturation temperature.

- A Reactor Coolant pump shall not be started with one or more of thc Reactor fy Coolant System cold leg temperatures less than or equal.to that specified in K.

Table 3.4-3 when the secondary water temperature of each steam generator is k

greater than 100'F above each of the Reactor Coolant System cold leg I

k temperatures.

7p g

SAN ONOFRE - UNIT 3 3/4 4-5 AMENOMENT NO. M

~

e 4.

s.;

I' p-'

REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED e

f SURVEILLANCE REOUIREMENTS s

[

4.4.1.4.1.1 The required Reactor Cooling pump (s), if not in operation, shall J;

be determined to be OPERABLE once per 7 days by verifying correct breaker align-i ments and indicated power availability.

[

p.

4.4.1.4.1.2 The required steam generator (s) shall be determined OPERABLE by verifying the secondary side water level to be >10% (wide range) at least once i

per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b

4.4.1.4.1.3 At least one Reactor Coolant loop or shutdown cooling train shall i

be verified to be in operation and circulating Reactor Coolant at least once 4;

per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

a 1:

l Ey

+t 4 -/.

p a

D 7

+?

y.

a O

t:7 6

77; h/

O

%ny 1:

r

&s

[w

?

4 110V 0 9 1984 y

AMENDMENT NO. 16

(

SAN ONOFRE - UNIT 3 3/4 4-Sa

I f,

- m

. 4 [.

3.,

t 3

_(%

REACTOR COOLANT SYSTEM k

COLD $ HUT 00b-LOOPSNOTFILLE0-I I'

LIMITING CONDITION FOR OPERATION r.

d 3.4.1.4.2 Two.shutdowncooling.trainsshallbeOPERA8LEfandatleastone shutdown cooling train shall be in operation.*

4 APPLICABILITY: MODE 5 with Reactor Coolant locps not filled.

ACTION:

With less than the above required trains OPERABLE, immediately

'I a.

initiate corrective action to return the required trains to OPERABLE h

status as soon as possible.

n b.

With no shutdown co'oling trains in operation, suspend all operations t

involving a reduction in boron concentration of the Reactor Coolant

' ).

System and immeoiately initiate corrective action to return the L

required shutdown cooling train to operation.

^

[

(~

t

(

??

.,f SURVEILLANCE REQUIREMENTS 4.4.1.4.2 At least one shutdown cooling train shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

k

-l

ne shutdown cooling train may be inoperable for up to'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance 0testing provided the other shutdown cooling train. -is OPERABLE and in operation..

-a c

-Y.

L The shutdown cooling pump may be de-energized for up to I hour provided 1) no-C h

operations are permitted that would causa dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is_ maintained at

~ '

k least 10*F below saturation temperature.

$$ t

~

w

/

__)iDV15 Igg?

g 4

.k

' SAN:0NOFRE-UNIT 3-3/4 4-6 y

j e[e;.

k 1

(j REFUELIM OPERAttow$

r i

3/4.9.8 $HUTDOW C00 LIM AND C00LAKf CIRCULATION

.._ _. 3!GH VAtt1t t,tYtt, f

L!klTTM CONDITION FOR 0PERATION l

h.

3.3.0.1 A s

operation ) Isast one' shutdown cooling train shall be OPEAA8LE and in p-j APPLICMILITY: M0E 6 when the vatar level above the top of the reacter 4

f pnseure vessel flange is gnatar than or equal to 23 feet.

i ACTION:

o I

With no shutdown cooling train CPERABLE and in operation, suspend all coerations

[

involving an increase in the reactor decay heat load or a reduction in boren i

concentration of the Reactor Coolant Systee and immediately initiata cornetive i

action to return the required shutdown cooling train to CPERA8LE and operating 1

status as soon as possible. Close all containment penetrations provicing dirtet access from the contaiteent staosphere to the outside atmosphere within

/.. y 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

{b

(

N tj

}

b f

SURVE!LLANCE REQUIREMENTS h

h 4.9.8.1 At least one shutdown cooling train shall be verified to be M operation and circulating nactor coolant at a flow rate of gnater than or 4

equal to 2200 gpa at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l n

3 fl

'The shutdown cooling train may be removed free oceration for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per

(

8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months peri:4 during the performance of CORE ALTERATICKS in the vicinity of g.

the reactor pressure vessel hot legs.

8

[,

d D,.

p p

f SAM ONOFRE-UNIT 3 3/4 9 3 AENDENT NO. 34 y

,e N

fa,

_ _ _ _. _ _ _ _ _ - _ _ - - _ - - - - - - - - - - - - - - - - - - - - - ^ ^ ' - ' ~ " ' ' ' ^ ^ ^ ~ ^ ' ~ ~ ~ ~

~

9 t

b{

REFUELING OPERATIONS

{

)

U LOW WATER LEVEL b

t LIMITING CONDITION FOR OPERATION g.

.=

t 9

3.g.8.2 Two independent shutdown cooling trains shall be OPERA 8LE and at h,

least one shutdown, cooling train shall be in operation.d APPLICMILITY: H0bE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

I'-

a.

With less than the required shutdown cooling trains OPERMLE.

[

terwdiately initiate, corrective action to return the required h

shutdown cooling trains to OPERABLE status, or to establish greater Y

than or equal to 23 feet of water above the reactor pressure vessel E) flange as soon as possible.

(

b.

With no shutdown cooling train in operation, suspend all operations o

involving a reduction in boron concentration of the Reactor Coolant T

System and imediately initiate corrective action to return the f

required shutdown cooling train to operation. Close all containmed g

penetrations providing direct access from the containment atmosphere

{,..,

to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

s s

k.?

r r

h

$URVEILLANCE REQUIREMENTS V

4.9.8.2 At least one shutdown cooling train shall be verified to be in g

operation and circulating reactor coolant at a flow rate of greater than or

[

equal to 2200 g;n at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

h t

it7 g

l

Both thutdown cooling trains may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period during the performance of CORE ALTERATIONS in

[

the vicinity of the reactor pressure vessel hot legs provided all t

operations involving a reduction in boron concentration of the RCS are h'

suspended.

w Q. l g.

.g k

SAN ON0FRE. UNIT 3 3/4 9 9 I,

r it i

t 1

d.

3/4.4 REACTOR COOLANT SYSTEM s'

[

BASES

(

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

[*

The plant is designed to operate with both reactor coolant loops and

(

associated reactor coolant pumps (RCPs)in operation, and maintain DNBR greater e

than 1.31 during all normal operations and anticipated transients.

As a i

result, in MODES 1 and 2 with one reactor coolant loop not in operation, this k

specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months K

since no safety analysis has been conducted for operation with less than four f

reactor coolant pumps or less than two reacto'r coolant loops in operation.

j In MODE 3, a single reactor coolant loop provides sufficient-heat removal capability for removing decay heat; however, single failure considerations g

recuire that two loops be OPERABLE.

j In MODE 4, and in MODE 5 with reactor coolant loops filled, a single f

reactor coolant loop or shutdown cooling train provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops / trains (either RCS or shutdown cooling) be OPERABLE.

w y

In MODE 5 sith reactor coolant loops not filled, a single shutdown cooling b

train provides sufficient heat removal capability for removing decay heat; Dut single failure considerations, and the unavailability of the steam genera-tors as a heat removing component, require that at least two shutdown cooling trains be OPERABLE.

The operation of one reactor coolant pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce

/

gradual reactivity changes during boron concentration reductions in the Reac-ter Coolant System.

The reactivity change rate associated with boron reductions will therefore, be within the capability of operator recognition and control.

The restrictions on starting a reactor coolant pump in MODES 4 and 5 with one or more RCS cold legs less than or equal to that specified in Table 3.4-3 l

are provided to prevent RCS pressure transients, caused by energy additinos from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50.

The RCS will be protected against overpressure transients and q

will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant a

to expand into or (2) by restricting starting of the RCPs to when the secondary 4

water temperature of each steam generator is less than 100*F above each of the g

RCS cold leg temperatures.

77 3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being R

pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve 4.6 x 105 lbs per hour of saturated steam at the valve setpoint e7 plus 3% accumulation.

The relief capacity of a single safety valve is adeouate j

to relieve any overpressure condition which could occur during shutdown with t

RCS cold leg temperature greater than that specified in Table 3.4-3.

In the event I

that no safety valves are OPERABLE and for RCS cold le equal to 285 F, the operating shutdown cooling relief *g temperature less than or g

1 valve, connected to the 7}

RCS, provides overpressure relief capability and will prevent RCS

)

overpressurization.

(

l P

SAN ON0FRE-UNIT 3 8 3/4 4-1 AMEN 0 MENT NO. 71 h

,p l I

's REFUELING OPERATIONS

/ '%

/

BASES 3/4.9.7 FUEL HANDLING MACHINE - SPENT FUEL STORAGE BUILDING (Continued) 1.

The radiological consequences due to complete rupture of all spent fuel assemblies in the spent fuel pool and the cask pool (480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses.

This analysis takes no credit for fuel handling building filters.(i.e., the fuel handling building hatches are open).

2.

Any possible distortion of all fuel assemblies and racks will not.

resultinacriticalarrayandK[$1 Specification 5.6," Fuel will remain less than 0.95, as longasfuelisstoredperTechnT Storage," and 3.9.13, " Spent Fuel Pool Boron Concentration."

j.

3/4.9.8 SHUTOOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) :'.f'f i;t.t ::; ling capacity is available to remove decay heat and main-tain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a com-plete loss of decay heat removal capacity.

With the reactor vessel head re-moved and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of.the operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures-to cool the core.

l i

i t

4 i?

s

-r 4

SAN ONOFRE - UNIT 3 B 3/4 9-2a AMENDMENT NO. 77 i

- -.,, -. -.., _, - ~, - -

t NPf-10/15-411 ATTACliMENT "C" REVISED SPEClflCATIONS UNIT 2 22----,-y,-e-,

~.,

y,r. er---ww-r-re,-

--~4ev=r,----

T-r--

1 r

a d

--4---"--

- r-

~

-r--

REALTOR COOLANT SYSTEM LOLD SHV1DOWN - LOOPS FILLEQ LIMITING CONDIT10N FOR OPERATION 3.4.1.4.1 a.

At least one of the following loop (s)/ trains listed below shall be OPERABLE and in operation *:

1.

Reactor Coolant Loop 1 and its associated steam generator and at least one associated Reactor Coolant Pump **

2.

Reactor Coolant Loop 2 and its associated steam generator and at least one associated Reactor Coolant Pump **

3.

Shutdown Cooling Train A***

4.

Shutdown Cocling Train B*=**

b.

One additional Reactor Coolant Loop / shutdown cooling train *"

shall be OPERABLE, or t

c.

The secondary side water level of each steam generator _shall be greater than 10% (wide range).

APPLICABILITY: MODE 5, with Reactor Coolant loops filled.

ACTI0h:

a.

With less than the above required shutdown trains / loops OPERABLE or with less than the required steam generator level, immediately initiate corrective action to return the required trains / loops to OPERABLE status or restore the required level as soon as possible.

b.

With no loop / train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required loop / train to operation.

All reactor coolant pumps and pumps"proViding^jshutdown cooling pumps may be de-energized for up to I hour provided'(1)~no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.

- A Reactor Coolant pump shall not be started with 'one'or more of the Reactor Coolant System cold leg temperatures less than or equal to that specified in Table 3.4-3 when the secondary water tem)erature of each steam generator is greater than 100*F above each of tie Reactor Coolant System cold leg temperatures.

7 A7 containment 1sp~ ay~ pump mays beru' sed fin: place! ofJailow! pressure) safety r

injectionipumpato provide-sh'utdown cooling" flow pr6vided the' reacto'r' has been sub-critical ;for a: period greaterithan 24l hours andtthe" reactor:c'oolant1 system <is ful.ly depressurized 'and ventedlintaccordan'ce withTS:3.4.8.3jl.b.L(Subsequent'tofimplementation1ofLDCPl2-6Bf3)/

SAN ON0FRE - UNIT 2 3/4'4-5 AMENDMENT NO. xxx L

i

i REACTOR COOLANT SYSTIM COLD SHUTDOWN - LOOPS FILLE (L SURVEILLANCE RE0ViRfMfNTS 4.4.1.4.1.1 The requit

7 actor Cooling pum)(s), if not in operation, shall be determined to be Oh t. once per 7 days ay verifying correct breaker alignments and indicate sower availability.

4.4.1.4.1.2 1he recuired steam generator (s) shall be determined OPERABLE by verifying the secondary side water level to be n10% (wide range) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.3 At least one Reactor Coolant loop or shutdown cooling train shall be verified to be in operation and circulating Reactor Coolant at least once por 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t i

I i

l..

I' SAN ON0fRE - UNIT 2 3/4 4-Sa--

AMENDMENT ~d0. xxx l-u

s.. a..

y

l REACTOR COOLANT SYSTEM COLD SHUJDOWN - LOOPS NOT Filled LlHITING CONDlil0N FOR OPERATION 3.4.1.4.2 Two shutdown cooling trains shall be OPERABLE' and at least one shutdown cooling train shall be in operation.* F **

APPLICABILITY: MODE 5 with Reactor Coolant loops not filled.

ACTION:

a.

With less than the above required trains OPERABLE, immediately initiate corrective action to return the required trains to OPERABLE status as soon as possible, b.

With no shutdown cooling trains in o)eration, suspend all operations involving a reduction in )oron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation.

SURVElltANCE REQUIREMENTS 4.4.1.4.2 At least one shutdown cooling train shall be determined to be in operation and circulating reactor coolant at least or.ce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' One shutdown cooling train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling train is OPERABLE and in operation.

The pump ^providing(shutdown cooling pump may be de-energized for up to I hour provided 1)~ no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.

* [ A coht'a i nmen t "s p ray' pump 1may l bei u s ed i n' p1 ace' o f W 1 oW p re s su re 3a fety injection piimp tol provide shutdown? cooling flow:provided the reactor hh

~

beenisub; critical for'a-period greater;than!24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and4the;reactof '

coolant' system is fully depressurized and-vented'in-accordance;withi:TS 3 A8.3.1.b.- (Subsequentnto implementation' of DCPz 2-6863)~

x l

SAN 0NOFRE - UNIT 2 3/4 4-6 AMENDMENT N0. xxx L

REFUEllNG OPERATIONS 3/4.9.8 SilVTDOWN C0011M AND COOLANT CIRCULATION HIGil WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in operation.U APPLICABILITY:

Mode 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling train OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVFIti ANCE Rf0VIRfMfNTS 4.9.8.1 a.

At least one shutdown cooling train shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l-The shutdown cooling train may be removed from operation for up to I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

Tcontainment' spray *pu_mpmaybe7usedinTplacelofT1oKpfessure"safet9

~ injection / pump'to provide shutdown cooling ~ flow. (Subsequentito~

_ implementation of;0CP 2-6863)

~^

~'

L SAN ON0FRE-UNIT 2 3/4 9-8 AMENDMENT No. xxx

t REFUELING OPER411QHS LOW WATER LEVIL llHITING CONDITION FOR OPERATION r

3.9.8.2 Two independent shutdown cooling trains shall be OPERABLE and at least one shutdown cooling train shall be in operation.d/

1 APPLICABillTY: Mode 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

t ACT10ti:

i a.

With less that the required shutdown cooling trains OPERABLE, l

immediately initiate corrective action to return the required shutdown cooling trains to OPERABLE status, or to establish grater than or equal to 23 feet of water above the reactor pressure vessel flange as soon as possible.

b.

With no shutdown cooling train OPERABLE and in operation, suspend all L

operations involving a reduction in boron concentration of the Reactor l

Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

I i

SURVfill ANCE RE0VIREMENTS L

4.9.8.2 At least one shutdown cooling train shall be verified to be in L

operation and circulating reactor coolant at a flow rate of l

greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

TA"containme'nt spray; pump may be~used in place of.a' low pressurefsa'fety

" injection pump;to provide shutdownLeocling_flowJ(Subsequent to~ ~

L

implementationlof DCP 2t6863)'

~

" ~ ~

f l'

i L

SAN ONOFRE UNIT 2 3/4 9 AMENDMENT No. xxx l

. _ ~ -

M4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor Coolant pumps in operation, and maintain DNBR greater than 1.31 during all normal operations and anticipated transients. As a result, in MODES 1 and 2 with one reactor coolant loop not in operation, this specification requires that the plant be in at least fl0T STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months since no safety analysis has been conducted for operation with less than 4 reactor coolant pumps or less than two reactor coolant loops in operation.

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODE 4, and in MODE 5 -with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling train provides sufficient heat removal capability for removing / trains (either RCS or shutdown cooling) bedecay require that at least two loops OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single shutdown cooling train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling trains be OPERABLE.

may be used inLplace of a low pressure safety injection?(LPSI)praf:(CS) pu In MODE SL (loops filled or loops not-filled)Ea' containment: s pum) to provide shutdown coolingi(SDC). flow: based on thejcalculated; heat load'of-tieTcore 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the reactor is~ sub-critical:with the reactor. coolant system?(RCS) fully depressurized and; vented;in accordance with TS ^3.4.8.3.1.b1 '

~~~

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing,. prevent stratification-and produce gradual reactivity changes during boron concentration reductions in the Reac-tor Coolant System. The reactivity change rate associated with boron reduc-tions will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump in Modes 4 and 5 with.

one or more RCS cold legs less than or equal to 235'F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be-SAN ON0FRE-UNIT 2 B 3/4 4-1 AMENDMENT NO. xxx

protected against overpressure transients and will not exceed the limits of Aapendix G by either (1) restricting the water volume in the pressurizer and t1ereby providing a volume for the primary coolant to expand into or-(2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 100*F above each of the RCS cold leg temper-atures.

3/4.4.2 SAFETY VALVES l-The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia. Each safety valve is designed 6

to relieve 4.6 x 10 lbs per hour of saturated steam at the valve setpoint plus 3% accumulation. The. relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with-RCS cold leg temperature greater than 235'F. In the event that no safety valves-are OPERABLE and for RCS cold leg temperature less than or equal-to that specified in Table 3.4-3, the operating shutdown cooling relief valve, connected to the RCS, provides overpressure relief capability and will prevent RCS over-pressurization.

i l

SAN ONOFRE-UNIT 2f A 3/4;441a;

'AMENDMENTEN0Dxxx

o REFUELING OPERATIONS BASES 3/4.9.7 FUEL HANDLING MACHINE - SfENT FUEL STORAGE BUILDING (Continued) 1.

The radiological consequences due to complete rupture of all spent fuel assemblies in the spent fuel pool and the cask pool (480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses as long as spent fuel has received a minimum of 88 days decay time.

This analysis takes no credit for fuel handling building filters (i.e., the fuel handling building hatches are open).

2.

Any possible distortion of all fuel assemblies and racks will not result in a critical array and Keff will remain less than 0.95, as long as fuel is stored per Technical Specifications 5.6, " fuel Storage," and 3.9.13, " Spent fuel Pool Boron Concentration."

3/4.9.8 SHUTDOWN COOLING AND C09 TANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*f as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent baron stratification.

In MODE 6 a containment spray (CS). pump'may be, used in place' of the~ low pressure safety iniection (LPSI) pump to provide shutdown cooling;(SDC)' flow.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capacity. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

i I

SAN ONOFRE - UNIT 2 B 3/4 9-2a AMENDMENT N0. xxx

I 3

NPF-10/15-411 l

i i

t i

t

[

ATTACHMENT "D" REVISED SPEClflCATIONS UNIT 3 1

v 4

Y

REACTOR CQQLANT SYM G C010 SHUQOWN - LOOPS fillEQ llMITING CONDlil0N FOR OPfRATION 3.4.1.4.1 a.

Atleastoneofthefollowingloop(s)/trainslistedbelow shall be OPERABLE and in operation *:

1.

Reactor Coolant Loop 1 and its associated steam generator and et least one associated Reactor Coolant Pump **

?,

Reactor Coolant Loop 2 and its associated steam generator and at least one associated Reactor Coolant Pump **

3.

Shutdown Cooling 1 rain A "

?

4.

Shutdown Cooling Train IC b.

One additional Reactor Coolant Loop / shutdown cooling train!"

shall be OPERABLE, or c.

The secondary side water level of each steam generator shall be greater than 10's (wide range).

APPLi(_AJJJ11Y: MODE 5, with Reactor Coolant loops filled.

ACT10N:

a.

With less than the above required shutdown trains / loops OPERABLE or with less than the required steam generator level, immediately initiate corrective action to return the required trains / loops to OPERABLE status or restore the required level as soon as possible.

b.

With no loop / train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required loop / train to operation.

F All reactor coolant pumps and pumps pd"(1)"no* operations are permitted that roviding1 shutdown cooling pumps may be de-energized for up to I hour provide would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

l

- A Reactor Coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to that specified in Table 3.4-3 when the secondary water temierature'of each steam generator is greater than 100*F above each of t1e Reactor Coolant -

System cold leg temperatures.

' A"conteinmentispray'pumpimay be used;in' placeJoffallo(p essur6 :safet

' injection pumpito provideFshutdo[wn coolingiflow providedithe reactor' /

l has been sub-critical;for a period greater than:24~hoursiandithe"

~

reactor coolantisystemois fully!depressurized and vented (inlaccordan~ce WithjTS 3.4.8.3.h b ((Subsequent"tolimplementa,tionfof;HMPi3j6863)] ~ '

SAN ON0FRE - UNIT 3 3/4 4-5 AMENDMENT NO. xxx

E[A(JDR COOLAlli SYSTEM COLD SHUTDOWN - LOOPS FILLED _

SVRVElltANCF RTOUIREMfNTS 4.4.1.4.1.1 The required Reactor Cooling pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.4.1.2 The required steam generator (s) shall be determined OPERABLE by verifving the secondary side water level to be 210% (wide range) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.4.1.3 At least one Reactor Coolant loop or shutdown cooling train shall be verified to be in operation and circulating Reactor Coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SAN ON0FRE - UNIT 3 3/4 4-Sa AMENDMENT NO. xxx

t REACTOR COOLANT SYSTEM DOLD SHVTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two shutdown cooling trains shall be OPERABLE' and at least one shutdown cooling train shall be in operation.*, y APPLICABILITY: MODE 5 with Reactor Coolant loops not filled.

ACTION:

a.

With less than the above required trains OPERABLE, immediately initiate corrective action to return the required trains to OPERABLE status as soon as possible.

b.

With no shutdown cooling trains in o)eration, suspend all operations involving a reduction in )oron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation.

SURVFilLANCE REQUIREMENTS 4.4.1.4.2 At least one shutdown cooling train shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' One shutdown cooling train may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other shutdown cooling train is OPERABLE and in operation.

The pump providi_ng l shutdown cooling pamp n.ay be de-energized for up to I hour provided 1) no operations are permitted that would cause dilution of the Reactor Coelant System boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.

- LA containment spray pump 1may.be/Used'in place 1o ra lowTpressure? safety injection _' pump-to provide shutdown cooling. flow, providedLtheireactor> has beenisub-critical' for a ' period _ greater thanJ24 hours and -'theTreactor' coolant l system is' fully depressurized;and vented in'accordancelwith -TS 3.4. 8.3.1.b. ;(Subsequent ttofimplementationfof MMP 3-6863)f " ' '

' ^

1 l

L SAN ONOFRE - UNIT 3 3/4 4-6 AMENDMENT NO. xxx-

=

r ve= = - +

t g-ew-aw ytw-w-

m e

eWg e-

?

REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATIQH lilGH WATER LEVEL tiMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be GPERABLE and in operation.'*

APPLICABILITY:

Mode 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACILQH:

With no shutdown cooling train OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVElllANCE REQUIREMENTS 4.9.8.1 a.

At least one shutdown cooling train shall be vr ^ 4ed to be in operation and circulating reactor coolant at a o rate of greater than or equal to 2200 gpm at least once ier 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The shutdown cooling train may be removed from operation for up to I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pe. iod during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

spray pump ma' l be use_d in! p1a'ce 'of allo [pressurf safety

W conta'inmentO

~ y

~

injection pump' to provide shutdown' cooling flow..(Subsequent.-to implementation;of MMP_3-6863)

SAN ONOFRE-UNIT 3 3/4 9-8 AMENDMENT No. xxx

REFUELING OflRATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling trains shall bt least one shutdown cooling train shall be in operation.O.0PERABLE and at APPLICABILITY: Mode 6 when the water level above the top of the reactor pressure vessel flance is less than 23 feet.

ACTION:

a.

With less tnat the required shutdown cooling trains OPERABLE, immediatcly initiate corrective action to return the required shutdown cooling trains to OPERAB!.E status, or to establish grater than or equal to 23 feet of water above the reactor pressure vessel flange as soon as

possible, b.

With no shutdown cooling train OPERABLE and in operation, suspend all-operations involving a reduction-in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation. Close all containment-penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVElltANCE RE001REMENTS 4.9.8.2 At least one shutdown cooling train shall be verified to be in operation and circulating reactor coolant-at a flow rate of greater than'or equal to 2200 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Both shutdown cooling trains may be removed from operation for up to 1-hour per 8-hour period during.the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs provided all-operations-involvingareductioninboronconcentrationoftheRCSaresuspenged.

TCAlontaininent7spraffpump may'beinsed[in'plFWoffiiloWpM40r#Tsafetf

" Einje' tion pump;tof;MMPc3'6863)fto..providershutdown cooling'" ;~ok.l(Subs

~

c a

jmplement,ation

~^

"~~

l SAN ON0FRE-UNIT 3 3/4 9-9 AMENDMENT No. xxx

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor Coolant pumps in operation, and maintain DNBR greater than 1.31 during all normal operations and anticipated transients. As a result, in MODES 1 and 2 with one reactor coolant loop not in operation, this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months since no safety analysis has been conducted for operation with less than 4 reactor coolant pumps or less than two reactor coolant loops in operation.

In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE.

In MODE 4, and in MODE 5 -with reactor coolant loops filled, a single reactor coolant loop or shutdown cooling train provides sufficient heat decay heat; but single failure considerations removal capability for removing / trains (either RCS or shutdown cooling) be require that at least two loops OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single shutdown cooling train provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two shutdown cooling trains be OPERABLE.

In MODE;Sr(loops 1 filled orlloops' notifilled)'1aicont'ainment spray T(CS)1 pump may be used in place of a low: pressurecsafetylinjection l(LPSI);pum6to provide f

shutdown cooling 1(SDC) flow based on the calculated heatlload ofitie core 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the reactor:is sub-critical 1withJthe: reactor coolantisystem (RCS) fully depressurized and vented in accordance with:T503.4.8;3;.1.b i "

~

The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reac-tor Coolaat System. The reactivity change rate associated with boron reduc-tions will, therefore, be within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump in Modes 4 and 5 with one or more RCS cold legs less than or equal to 235'F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be SAN ON0FRE-UNIT 3 8 3/4 4-1 AMENDMENT NO. xxx

protected against overprest re transients and will not exceed the limits of Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restricting starting of the RCps to when the secondary water temperature of each steam generator is less than 100*F above each of the RCS cold leg temper-atures.

3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia. Each safety valve is designed 6

to relieve 4.6 x 10 lbs per hour of saturated steam at the valve setpoint plus 3% accumulation. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with RCS cold leg temperature greater than 235*F. In the event that no safety valves are OPERABLE and for RCS cold leg temperature less than or equal to that specified in Table 3.4-3, the operating shutdown cooling relief valve, connected to the RCS, provides overpressure relief _ capability and will-prevent RCS over-pressurization.

SANOOFRE-UNIT?31 B3/414-lal 1.~ AMEN 0MENTNO{xn

I REFUELING OPERATIONS BASES 3/4.9.7 FUEL HANjlllNG MA_C111NE - SPENT FUEL STORAGE BUILDING (Continued) 1.

The radiological consequences due to complete rupture of all spent fuel assemblies in the spent fuel pool and the cask pool (480 maximum), will remain below (less than 25% of) the exposure limits of 10 CFR 100 for offsite doses as long as spent fuel has received a minimum of 88 days decay time.

This analysis takes no credit for fuel handling building filters (i.e., the fuel handling building hatches are open).

2.

Any possible distortion of all fuel assemblies-and racks will not result in a critical array and Keff will remain less than 0.95, as long as fuel is stored per Technical Specifications 5.6, " Fuel Storage," and 3.9.13, " Spent Fuel Pool Boron Concentration."

3/4.9.8 SHVTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

In' MODE'6-a containment spray (CS)1 pump may be used' in"pla'cfofTthe710w pressure safety injection (LPSI) pump to provide shutdown cooling;;(SDC)fflow.

The requirement to have two shutdown cooling trains OPERABLE when there is less than E3 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capacity. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

SAN ONOFRE - UNIT 3 B 3/4 9-2a AMENDMENT NO. xxx

s NPF-10/15-411 ec ATTACHMENT "E" SUPPORTING FIGURES REFERENCED IN PCN 411

a R

T 2

N E 1

D E. E n

A G

t E

@H r

L f

A' Y yE O

R T

T A2 NR D

H OOPo A

TCSt O

E M

T H

OR F

H

[!

9)v5%

035 G

I!

l l

g8 e

1 lI

+

l y

m' m

m 7

Mg$e*

se8 TNL L 4

4 4

EEO PUO pT.

SFP

?

T' M 1 i ti 1'

1

!I O

A j

O 4 l

]

1I

!I F

1 l

2 l

iq

,i e

,i gnahC UX MX 50 d

0 es M

opo 1

0 r

5 I

P 5

1 1

0 1

8 0

4 e

6 9

r V

U V

3 7

ot)

H M

H 3

3 f

n 9

4 e

,y V

e 3

V Bm r

A3 H

H 4

4 n n M

NU h k o

ig M

t i M

l aA ru1 ig e m'

fnd o o N

5 5

CM 9

3

(

3 3

1 S

9 m

l 6 g p

1 e

4 t

3

(

V s

l '

1 y

4M O 7 O

H S

E l

>V

)

H U

1 0

(

64g M

E 1

RU VH G

IF 0W 2

3 5

5 s

1 2

f 4

V vH H

~

g31__y 2 8 V

E 9 4

Y T

1 Fg O

E 1

T 5 2

23 E 8 Fy l

2Q

[

E 3

0 F1 2

7

[

BO S

3 6

5 1

1 1

U 0

0 0

M P

P P

8 s

\\s o

o

?

ot u

N M

4 M

s

ic

-8l_

8l g

h 1:

2 R

9 9. 9-l 8

IN3r4NIVINO3 -

t m

ei :

lif$

g_e:

ei:@ei:

s

=

-e e o

e h~S 8

a a

2 s

rc :p a-5

=~

NQl4i'b s

6 r

,l p8

-g g

'5

->44><

4

? U g

g

" y ag g "g <5"l u

a a

!p&

m g

9 8

3 9"

r s

9 a

te 0-$ s!

N 5

0 en ei

.{d g

u y_

g r

g

=

Ok 3

g *g@4 ~i i

_e 58 ll0 @l E

g g

~_

3 s

0

." --,L _

n_

.,,,.-,,m" _:p.

n=

4 k

u=

k l

L 1

ea: !i eses es: ::

l.

+

~

u

ll3 30 s

+

t R h$

Shk-$

1 IN3r4NIVINO3 ggy,-- -. _ _.

A 4

g a

o sino a

lid k

&f

&I@#[

@#[

8

?

j ee 7

-4+

s-

.e s

s s

s m,. m um m m m,s.

s h

s g

s e

s O-i

(

I!

?

\\::

3':r we-t e=

e i

Eg c"R i i

.t, v; i

BE

E>lt{

ll Jm'c Em*m *g

, r it o

4

\\ g e

em; u a:s s

s s

g u

so

(

2 s

g a

s

.91 as ES 8 s

3 9

s co k

00 n

g' P

1 P s

E 8

I g

k-k

~ 7 g

>s v) a J

k

~

G4F V

T r

3 S

kb g

g t m da sm<

j g

s m

s g

yx w:

m s

g!

O=

F-' l s

s

,mmmxm4 m,,

.r

.r 2

s s

hg

+

~

u g

wqu, g u

eso k

L 2

m g

7 7

6.

@E8 gg:

t!

66 C

y y 19 19 a

b F

H I

-O aa

.,e s

i ua-->

_ _ h._._.

.._{.} ja N1 l

g i

4 mum u

e

$$b OM[ d

&lI

h d @M[

T i

T T

H_

E ft g[+"g;.

gy m_,A am_a i

138.

i l

8e s

}

k

""g

=

i i

=

s

@-h

(

j gymEl f

j g

A

_a v

i

- M R!

[.

h 8.

l 5l 4llv;{

J&

tm<mJ l

EE

-lt u

o "n

'\\?

i 4

emR ;p s

a 8.$

s E

5 is a

a s-E S

E

\\

c d8 g

k0 ll M[M :

[j 9d"'

4 r

3 m

e e

s E

3

5 a!

[

-N

~ ><

ng 1

p m x, x m m g T

"l 62

ea emmm[- mm<mmmm<mmyummmmmms

=

s ~a L

L s

e i

hEhl bEbE E $l 9,

5 u<-

u

+

I d5 3 r 3 r d'

l' 6

--+hh E

f a

jL u

1 hh 6

6 EE U

l!

ea~

sa.

e oa 28h9 E889 22 g

E

{

k mmewoo -

__ _ 6__ _ _ h _ _ _ __[.} g3L,-- - - -- - -

t!

A i

4 g

u me,-

I k!NN l

&h

f

?@d[

'4T

[

er

@=

rB

=r y

- + = -

,_ m g

mm s m s; s

s s

smssum g3 y

i s

a a

s 4o s s

a w,,

i s

5 h

k n,

N[2*N i E

I

,r A

i s

o g

g h

k

(

g "6 a

s,e f: p s

sa

s s 4,_,

.i "h

&k >

h

\\

(s) ij

,0 ss a

s e

s s

g i'-

a

=

a a

s s

a E

s t

a a

s c

~~

Q6 s

3

& -0 ik h

k qk g

e h

~m x

s m

kb

$5 2

$g

=

z s

Ak 3

1 g

s

4:

'e<

A r$

t es

~

._s

-~

h 4,

4

}

?!

j i

BE I!

Eif08 i

8 i

9,

~

n

+

r' g

go s

u 4 z)[ s___/

h

_m _ _4 m _ s:

u s~.

.i

e-

+

MUOe7 2F0 t

.g 9414 l

2FE 2TE

' 'UN 0346 at4e TO-g CS

/"'""'

E003

'"'"/"r

?4

? N RAYHEAD R 2F0 u

HV4151 l

9426 p A

3 V

5uUw2

,n4+me i

l F '

HU4153

/

j

/

p a

MU993

/

l

/

l MU366 TW FOR RELOCATED

/

2TE C351-Y f

/

tj

'WSJ$

/'

t'/f1r l

f 'N"'

"/ p t

/

swa

/

4160 HV4161 F'

s pr/ W u n s uss>vnsrs und l

ns unssus NQsQs$

f

/

s 2 215 s,

/

8 tps d '

HV@96

@' ? 4 M ; ; N

$sssMwpps

/

E215 1P

/

I

/

MU367 p

p

/

h

'//

$sss}ll E

y

/

uumi

[

/

2Fo d,3

/

MUO88 2FE

- 9427 8

j

/

V u

Hv4150 To 0 38 C

AN

,, gs M%l*==- --

=> l E004 lmn;;;====mn-A_

ll74

-3 p y AD R MU105 NuU106 W1

/

A 2TE n

A s.-

us 61 6

/

N V

MuG18 92183

/

1

/

4

$ l b,g pscQ s ;;____.. g y

~

93'I "U**

ha =-._.

ammawww====. := g><} sacemq uul04

/

h N

l

/

=-

a f;_2m__..__

-w3g se I

T h

1 m__

g,

/

2,0 9317 f

y

, uu994

/

TO S E.B.

HV-9359 1r

/

CONTAMINATED

' 74 T

l

/

FLOOR DRAN e,1wssss,s Asssssssssssssssssssssssh s FnOu hat tEo,2 HV-9336 HV-9353

/

" HV-9379 l

/

y siss4 ssssssssssss/ 4,,s,ssssssssss,ss,ssis sis.

CS pump in SFP Service ns, rJoicATES FLCW pu p SC mb FIGURE (6) System Configuration After Proposed Change

.hP mame moicATESFLOW m__.. _ _ _ _ _--__

NPF-10/15-411 ATTACHMENT "F" POST DCP 2-6863/MMP 3-6863 MODIFICATIONS SPENT FUEL POOL COOLING ADMINISTRATIVE CONTROLS (INFORMATION ONLY)

a=

ATTACHMENT F-page 1 of 6 SPENT FUEL POOL COOLING SYSTEM Applicable to MODES 1 through 5 and MODE 6 prior to fuel movement from the core to the spent fuel pool.

LCO:

Maintain 2 spent fuel pool pumps and 2 spent fuel pool heat exchangers OPERABLE. Maintain 1 spent fuel pool pump and 1 spent fuel pool heat exchangroperatingtomaintainthespentfuelpooltemperature5 140*F APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6 prior to fuel movement from the core to the spent fuel pool.

I ACTION:

1.

With less than the required components OPERABLE, a.

Place fuel elements in _a safe location and suspend all fuel handling operations.

b.

Restore the INOPERABLE component to OPERABLE status prior to reaching 140*F or a maximum of 7 days, which ever is more restrictive.

Additionally, monitor the spent fuel pool temperature once-a shift, estimate the outage time available before reaching-140*F, and initiate actions to expedite the. return of the spent fuel pool cooling system to OPERABLE status, as~ required to maintain the spent fuel pool temperature below 140*F.

i)

If the outage duration extends past 7 days, prep'are a division incident report to identify the cause of the extended outage and identify corrective actions to limit future equipment outages to less than 7 days.

' I train of shutdown cooling (consisting of I containment spray pump or 1 low pressure safety injection pump and 1 shutdown cooling heat exchanger) may be used _as an alternative to 1 spent fuel pool cooling pump and 2 spent fuel pool cooling heat exchangers. NOTE: THE AB0VE NAMED COMPONENTS MAY NOTlBE-USED FOR COOLING THE SPENT FUEL P0OL IF THEY ARE REQUIRED TO BE "0PERABLE" BY ANY TECHNICAL SPECIFICATION

1 train of shutdown cooling operated in accordance with Technical Specification 3/4.9.8.1 and_ aligned to cool the spent fuel pool using an additional shutdown cooling pump with the mixed flow line up meets the requirement of this LCO.

l

O s

ATTACHMENT F page 2 of 6 ii)

If the spent fuel pool temperature exceeds 140*F prepara a Operations Division Experience Report (0 DER).

2.

With no spent fuel pool cooling system 0PERABLE, a.

Place fuel elements in a safe location and suspend all fuel handling operations.

b.

Restore at least 1 spent fuel pool cooling pump and I heat exchanger or 1 train of shutdown cooling to OPERABLE and operating prior to reatning 1406F or a maximum of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which ever is more restrictive.

Additionally, monitor the spent fuel pool temperature twice per shift, estimate the outage time available before reaching 140*F, and initiate actions to expedite the return of the spent fuel pool cooling system to OPERABLE status, as required to maintain the spent fuel pool temperature below 140*F.

i)

If I spent fuel pool cooling pump and I heat exchanger or 1 train of shutdown cooling are not restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , prepare a division incident report to identify the cause of the extended equipment outage and identify corrective actions to limit future equipment outages to less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , ii)

If the spent fuel pool temperature exceeds 140*F prepare a ODER.

iii)

If the spent fuel pool temperature reaches 212*F prepare a voluntary LER.

c.

Provide for makeup to the SFP as necessary SURVEILLANCE REQUIREMENTS The spent fuel pool cooling system shall be demonstrated OPERABLE:

Once per shift, verify spent fuel pool pump and spent fuel pool heat exchanger (or shutdown cooling equipment) operating and the spent fuel pool temperature

< 140*F.

Once per seven days, verify the spent fuel pool cooling system is OPERABLE by verifying the correct breaker alig1ments and power availability.

l

.e-v ATTACliMENT F-page 3 of 6 SPENT FUEL P00L COOLING SYSTEM Applicable to MODE 6 after commencing fuel movement from the core to the spent fuel pool for a refueling that does not result in a full core offload.

(Less than or equal to 109 fuel assemblies being transferred to the spent fuel pool)

LCO:

Maintain 2 spent fuel pool pumps and 2 spent fuel pool heat exchangers OPERABLE. Maintain 1 spent fuel pool pump and 2 spent fuel pool heat-exchanpersoperatingtomaintainthespentfuelpooltemperature5 140*F.

APPLICABILITY: MODE 6 after commencing fuel movement from the core to the spent fuel pool for a refueling that will not result in a full core offload.

(Less than or equal to 109 fuel assemblies being transferred to the spent fuel pool)

ACTION:

1.

With less than the required components OPERABLE, a.

Place fuel elements in a safe location and suspend all fuel handling operations.

b.

Restore the IN0PERABLE component to OPERABLE status prior to reaching 140*F or a maximum of 7 days, which ever is more restrictive.

During the equipment outage, monitor the spent fuel pool temperature once a shift, estimate the outage time available before reaching 140*F, and initiate actions to expedite the return of the spent fuel pool cooling system to OPERABLE status, as required to maintain the spent fuel pool temperature below 140'F.

i)

If the outage duration extends past 7 days, prepare a division incident report to identify the cause of the extended outage and identify corrective actions-to limit future equipment outages to less than-7 days.

' I train of shutdown cooling (consisting of I containment spray pump or 1 low pressure safety injection pump and 1 shutdown cooling heat exchanger) may be considered as an alternative to 2 spent fuel pool cooling pumps and 2 spent

-fuel pool cooling heat exchangers. However, the shutdown cooling train can only be considered available for spent fuel pool cooling when the shutdown cooling train is NOT required to be OPERABLE by Technical Specifications for core cooling.

1 train of shutdown cooling operated in accordance with Technical Specification 3/4.9.8.1 and aligned to cool the spent fuel pool using an additional shutdown cooling pump with the mixed flow line up meets the-requirement of this LCO,

ATTACHMENT F

page 4 of 6 11)

If the spent fuel pool temperature exceeds'140*F prepare a ODER.

iii)

If the spent fuel pool temperature reaches 212'F prepare a voluntary LER.

2.

With no spent fuel pool cooling system OPERABLE, a.

Place fuel elements in a safe location and suspend all fuel handling operations.

b.

Immediately restore at least 1 spent fuel pool cooling pump and 2 heat exchangers or 1 train of shutdown cooling to OPERABLE and operating.

Additionally, monitor the spent fuel pool temperature twice per shift.

1)

If the spent fuel pool temperature exceeds 140*F prepare a ODER.

11) Provide for makeup to the SFP is necessary to. replace lost inventory in the SFP.

iii)

If the spent fuel pool temperature reaches 212*F prepare a voluntary LER.

SURVEILLANCE REQUIREMENTS The spent fuel pool cooling system shall be demonstrated OPERABLE:

Once per shift, verify spent fuel pool pumps and_ spent fuel pool heat exchangers (or shutdown cooling equipment) are operating the spent fuel pool temperature < 140'F.

Once per seven days, verify the spent fuel pool cooling system is OPERABLE by verifying the correct breaker alignments and power availability.

.i. < 4 i

ATTACHMENT F page 5 of 6-SPENT FUEL P0OL COOLING SYSTEM Applicable to MODE 6 after commencing fuel movement from the core to the spent-fuel pool for a full core offload.

(Greater than 109 fuel assemblies being transferred to the spent fuel pool.)

LCO:

Maintain 2 spent fuel pool pumps and 2 spent fuel pool heat exchangers OPERABLE and operating to maintain the spent fuel pool temperature j

below 160*F. #

or Maintain 1 train of shutdown cooling (consisting of I containment spray pump or 1 low pressure safety injection pump and I shutdown cooling heat exchanger) OPERABLE and in operation cooling the spent fuel pool with the associated Diesel Generator OPERABLE.

(The shutdown cooling train can only be considered available for spent fuel pool cooling when the shutdown cooling train is NOT required to be OPERABLE by Technical Specifications.)

APPLICABILITY: MODE 6 after commencing fuel movement from the core to the spent fuel pool for a full core offload.

(Greater than 109-fuel assemblies being transferred to the spent fuel pool.)

ACTION:

1.

With less than the required components OPERABLE or with the spent fuel pool temperature greater than or equal to 160aF, a.

Place fuel elements in a safe location and suspend all fuel handling operations, b.

Immediately initiate action to restore at least 2 spent fuel pool cooling pumps and 2 heat exchangers to OPERABLE and operating, or Return I train of shutdown cooling 0PERABLE and in operation cooling the spent fuel' pool.

1 train of shutdown cooling operated in accordance with Technical Specification 3/4.9.8.1 and aligned to cool the spent fuel pool using an additional shutdown cooling pump with the mixed flow line up and maintaining-the spent fuel pool less-than 140*F meets the requirement of this LCO.

212af is the limiting temperature for the spent fuel pool licensing basis, however, the post accident cleanup units are not analyzed with the pool temperature in excess of 160*F.

),,u ATTACHMENT F page 6 of 6 Additionally, monitor the spent fuel pool temperature twice per shift.

1)

If the spent fuel pool temperature reaches 212*F prepare a voluntary LER, c.

Provide for makeup to the SFP as necessary to replace lost inventory in the SFP.

SURVEILLANCE REQUIREMENTS The spent fuel pool cooling system shall be demonstrated OPERABLE:

~

Once per shift, verify 2 spent fuel pool pumps and 2 spent fuel pool heat exchangers are operating, or Once per shift, verify I low pressure safety injection pump or 1 containment spray pump and I shutdown cooling heat exchanger are operating.

I

.

ML20126E788

Contents

Text

RESPONSE

RESPONSE

RESPONSE

Navigation menu

ML20126E788

Text

RESPONSE

RESPONSE

RESPONSE

Navigation menu

Search